## Contact

**KTH Royal Institute of Technology**

*SE-100 44 Stockholm Sweden +46 8 790 60 00*

[1]

F. Dehlin and J. Wallenius, "Activation analysis of the lead coolant in SUNRISE-LFR," *Nuclear Engineering and Design*, vol. 414, 2023.

[2]

F. Dehlin, J. Wallenius and S. Bortot, "An analytic approach to the design of passively safe lead-cooled reactors (vol 169, 108971, 2022)," *Annals of Nuclear Energy*, vol. 181, 2023.

[3]

Z.-N. Huang *et al.*, "Analysis of the stress field in the reactor vessel of the China Initiative Accelerator Driven System during postulated ULOF and UTOP transients," *Annals of Nuclear Energy*, vol. 194, 2023.

[4]

D. -. Wang *et al.*, "Finite element analysis of the main reactor vessel in the China Initiative Accelerator Driven System," *Engineering Failure Analysis*, vol. 146, 2023.

[5]

C. Reale Hernandez, J. Wallenius and J. Luxat, "Simulation of a loss of flow transient of a small Lead-Cooled reactor using a CFD-Based model," *Nuclear Engineering and Design*, vol. 412, 2023.

[6]

Y. Mishchenko *et al.*, "Thermophysical properties and oxidation behaviour of the U_{0.8}Zr_{0.2}N solid solution," *Nuclear Materials and Energy*, vol. 35, 2023.

[7]

G. Wang *et al.*, "Transient analyses for China initiative Accelerator Driven System using the extended BELLA code," *Annals of Nuclear Energy*, vol. 190, 2023.

[8]

F. Dehlin, J. Wallenius and S. Bortot, "An analytic approach to the design of passively safe lead-cooled reactors," *Annals of Nuclear Energy*, vol. 169, pp. 108971-108971, 2022.

[9]

J. Wallenius, "An improved correlation for gas release from nitride fuels," *Journal of Nuclear Materials*, vol. 558, 2022.

[10]

D. R. Costa *et al.*, "Coated ZrN sphere-UO_{2} composites as surrogates for UN-UO_{2} accident tolerant fuels," *Journal of Nuclear Materials*, vol. 567, pp. 153845, 2022.

[11]

C. R. Hernandez *et al.*, "Development of a CFD-based model to simulate loss of flow transients in a small lead-cooled reactor," *Nuclear Engineering and Design*, vol. 392, pp. 111773, 2022.

[12]

B. Xi *et al.*, "Influence of TIG and Laser Welding Processes of Fe-10Cr-4Al-RE Alloy Cracks Overlayed on 316L Steel Plate," *Materials*, vol. 15, no. 10, pp. 3541, 2022.

[13]

D. R. Costa *et al.*, "Interface interactions in UN-X-UO2 systems (X = V, Nb, Ta, Cr, Mo, W) by pressure-assisted diffusion experiments at 1773 K," *Journal of Nuclear Materials*, vol. 561, pp. 153554-153554, 2022.

[14]

Y. Mishchenko *et al.*, "Potential accident tolerant fuel candidate : Investigation of physical properties of the ternary phase U2CrN3," *Journal of Nuclear Materials*, vol. 568, 2022.

[15]

D.-S. Wang *et al.*, "Analysis of the Accelerator-Driven System Fuel Assembly during the Steam Generator Tube Rupture Accident," *Materials*, vol. 14, no. 8, 2021.

[16]

Y. Mishchenko *et al.*, "Design and fabrication of UN composites : From first principles to pellet production," *Journal of Nuclear Materials*, vol. 553, pp. 153047, 2021.

[17]

S. Yang *et al.*, "Development of a welding process to overlay FeCrAl alloy on a thin wall austenitic stainless steel tube," *Nuclear Materials and Energy*, vol. 27, 2021.

[18]

D. R. Costa *et al.*, "Oxidation of UN/U2N3-UO2 composites : an evaluation of UO(2 )as an oxidation barrier for the nitride phases," *Journal of Nuclear Materials*, vol. 544, 2021.

[19]

Y. Mishchenko *et al.*, "Uranium nitride advanced fuel : an evaluation of the oxidation resistance of coated and doped grains," *Journal of Nuclear Materials*, vol. 556, 2021.

[20]

J. Wallenius, "Anomalous reactivity swing in the 238U-233U system," *Annals of Nuclear Energy*, vol. 139, 2020.

[21]

C. Reale Hernandez, J. Wallenius and J. Luxat, "Dynamic sensitivity and uncertainty analysis of a small lead cooled reactor," *Annals of Nuclear Energy*, vol. 144, 2020.

[22]

C. Ekberg *et al.*, "Fuel fabrication and reprocessing issues : the ASGARD project," *EPJ Nuclear Sciences & Technologies.*, vol. 6, 2020.

[23]

D. R. Costa *et al.*, "UN microspheres embedded in UO2 matrix : An innovative accident tolerant fuel," *Journal of Nuclear Materials*, vol. 540, 2020.

[24]

J. Wallenius and S. Bortot, "A new paradigm for breeding of nuclear fuel," *Annals of Nuclear Energy*, vol. 133, pp. 816-819, 2019.

[25]

J. Wallenius, "Maximum efficiency nuclear waste transmutation," *Annals of Nuclear Energy*, vol. 125, pp. 74-79, 2019.

[26]

J. Wallenius and S. Bortot, "A small lead-cooled reactor with improved Am-burning and non-proliferation characteristics," *Annals of Nuclear Energy*, vol. 122, pp. 193-200, 2018.

[27]

J. Wallenius *et al.*, "Design of SEALER, a very small lead-cooled reactor for commercial power production in off-grid applications," *Nuclear Engineering and Design*, vol. 338, pp. 23-33, 2018.

[28]

K. Johnson *et al.*, "Oxidation of accident tolerant fuel candidates," *Journal of Nuclear Science and Technology*, vol. 54, no. 3, pp. 280-286, 2017.

[29]

E. Bubelis *et al.*, "System codes benchmarking on a low sodium void effect SFR heterogeneous core under ULOF conditions," *Nuclear Engineering and Design*, vol. 320, pp. 325-345, 2017.

[30]

K. D. Johnson *et al.*, "Fabrication and microstructural analysis of UN-U3Si2 composites for accident tolerant fuel applications," *Journal of Nuclear Materials*, vol. 477, pp. 18-23, 2016.

[31]

K. D. Johnson *et al.*, "Spark plasma sintering and porosity studies of uranium nitride," *Journal of Nuclear Materials*, vol. 473, pp. 13-17, 2016.

[32]

S. Bortot, E. Suvdantsetseg and J. Wallenius, "BELLA : a multi-point dynamics code for safety-informed design of fast reactors," *Annals of Nuclear Energy*, vol. 85, pp. 228-235, 2015.

[33]

P. R. Hania *et al.*, "Irradiation and post-irradiation examination of uranium-free nitride fuel," *Journal of Nuclear Materials*, vol. 466, pp. 597-605, 2015.

[34]

E. Suvdantsetseg and J. Wallenius, "An assessment of prompt neutron reproduction time in a reflector dominated fast critical system : ELECTRA," *Annals of Nuclear Energy*, vol. 71, pp. 159-165, 2014.

[35]

P. Malkki *et al.*, "Manufacture of fully dense uranium nitride pellets using hydride derived powders with spark plasma sintering," *Journal of Nuclear Materials*, vol. 452, no. 1-3, pp. 548-551, 2014.

[36]

Y. Zhang and J. Wallenius, "Upper limits to americium concentration in large sized sodium-cooled fast reactors loaded with metallic fuel," *Annals of Nuclear Energy*, vol. 70, pp. 180-187, 2014.

[37]

J. Zakova and J. Wallenius, "Multirecycling of Pu, Am and Cm in BWR," *Annals of Nuclear Energy*, vol. 58, pp. 255-267, 2013.

[38]

E. Suvdantsetseg, J. Wallenius and S. Bortot, "Optimization of the reactivity control drum system of ELECTRA (vol 252C, pg 209, 2012)," *Nuclear Engineering and Design*, vol. 255, pp. 376-376, 2013.

[39]

Y. Zhang, J. Wallenius and M. Jolkkonen, "Transmutation of americium in a large sized sodium-cooled fast reactor loaded with nitride fuel," *Annals of Nuclear Energy*, vol. 53, pp. 26-34, 2013.

[40]

J. Wallenius, E. Suvdantsetseg and A. Fokau, "Electra : European Lead-Cooled Training Reactor," *Nuclear Technology*, vol. 177, no. 3, pp. 303-313, 2012.

[41]

J. Zakova and J. Wallenius, "Fuel residence time in BWRs with nitride fuels," *Annals of Nuclear Energy*, vol. 47, pp. 182-191, 2012.

[42]

E. Suvdantsetseg, J. Wallenius and S. Bortot, "Optimization of the reactivity control drum system of ELECTRA," *Nuclear Engineering and Design*, vol. 252, no. 1, pp. 209-214, 2012.

[43]

J. Wallenius, "Physics of Americium transmutation," *Nuclear Engineering and Technology*, vol. 44, no. 2, pp. 199-206, 2012.

[44]

M. Tesinsky, Y. Zhang and J. Wallenius, "The impact of americium on the ULOF and UTOP transients of the European Lead-cooled SYstem (ELSY)," *Annals of Nuclear Energy*, vol. 47, pp. 104-109, 2012.

[45]

M. Tesinsky *et al.*, "The impact of americium on transients in the European Lead-cooled SYstem ELSY loaded with nitride fuel," *Annals of Nuclear Energy*, vol. 50, pp. 56-62, 2012.

[46]

J. Wallenius, N. Sandberg and K. Henriksson, "Atomistic modelling of the Fe-Cr-C system," *Journal of Nuclear Materials*, vol. 415, no. 3, pp. 316-319, 2011.

[47]

Y. Zhang *et al.*, "Physics and safety studies of a compact ADS design loaded with nitride fuel," *Annals of Nuclear Energy*, vol. 38, no. 11, pp. 2350-2355, 2011.

[48]

J. Zakova and J. Wallenius, "Void reactivity feedback in BWRs with MA bearing MOX fuels," *Annals of Nuclear Energy*, vol. 38, no. 9, pp. 1968-1977, 2011.

[49]

A. Fokau *et al.*, "A source efficient ADS for minor actinides burning," *Annals of Nuclear Energy*, vol. 37, no. 4, pp. 540-545, 2010.

[50]

Y. Zhang, J. Wallenius and A. Fokau, "Transmutation of americium in a medium size sodium cooled fast reactor design," *Annals of Nuclear Energy*, vol. 37, no. 5, pp. 629-638, 2010.

[51]

M. Pukari *et al.*, "Vacancy formation and solid solubility in the U-Zr-N system," *Journal of Nuclear Materials*, vol. 406, no. 3, pp. 351-355, 2010.

[52]

S. L. Dudarev *et al.*, "The EU programme for modelling radiation effects in fusion reactor materials : An overview of recent advances and future goals," *Journal of Nuclear Materials*, vol. 386, pp. 1-7, 2009.

[53]

W. Maschek *et al.*, "Accelerator driven systems for transmutation : Fuel development, design and safety," *Progress in nuclear energy (New series)*, vol. 50, no. 2-6, pp. 333-340, 2008.

[54]

K. O. E. Henriksson, N. Sandberg and J. Wallenius, "Carbides in stainless steels : Results from ab initio investigations," *Applied Physics Letters*, vol. 93, no. 19, 2008.

[55]

N. Sandberg, K. O. E. Henriksson and J. Wallenius, "Carbon impurity dissolution and migration in bcc Fe-Cr : First-principles calculations," *Physical Review B. Condensed Matter and Materials Physics*, vol. 78, no. 9, 2008.

[56]

J. Wallenius and D. Westlén, "Hafnium clad fuels for fast spectrum BWRs," *Annals of Nuclear Energy*, vol. 35, no. 1, pp. 60-67, 2008.

[57]

L. Malerba, A. Caro and J. Wallenius, "Multiscale modelling of radiation damage and phase transformations : The challenge of FeCr alloys," *Journal of Nuclear Materials*, vol. 382, no. 2-3, pp. 112-125, 2008.

[58]

P. Olsson, C. Domain and J. Wallenius, "Ab initio study of Cr interactions with point defects in bcc Fe," *Physical Review B. Condensed Matter and Materials Physics*, vol. 75, no. 1, pp. 014110, 2007.

[59]

V. Pontikis, V. Russier and J. Wallenius, "An analytic n-body potential for bcc iron," *Nuclear Instruments and Methods in Physics Research Section B : Beam Interactions with Materials and Atoms*, vol. 255, no. 1, pp. 37-40, 2007.

[60]

L. Malerba *et al.*, "Modelling of radiation damage in Fe-Cr alloys," *Journal of ASTM International*, vol. 4, no. 6, 2007.

[61]

J. Wallenius *et al.*, "Simulation of thermal ageing and radiation damage in Fe-Cr," *Nuclear Instruments and Methods in Physics Research Section B : Beam Interactions with Materials and Atoms*, vol. 255, no. 1, pp. 68-74, 2007.

[62]

N. Juslin *et al.*, "Simulation of threshold displacement energies in FeCr," *Nuclear Instruments and Methods in Physics Research Section B : Beam Interactions with Materials and Atoms*, vol. 255, no. 1, pp. 75-77, 2007.

[63]

K. Tucek *et al.*, "Studies of an accelerator-driven transuranium burner with hafnium-based inert matrix fuel," *Nuclear Technology*, vol. 157, no. 3, pp. 277-298, 2007.

[64]

D. A. Terentyev *et al.*, "Displacement cascades in Fe-Cr : A molecular dynamics study," *Journal of Nuclear Materials*, vol. 349, no. 1-2, pp. 119-132, 2006.

[65]

D. Terentyev *et al.*, "Effect of the interatomic potential on the features of displacement cascades in alpha-Fe : A molecular dynamics study," *Journal of Nuclear Materials*, vol. 351, no. 03-jan, pp. 65-77, 2006.

[66]

P. Olsson, I. A. Abrikosov and J. Wallenius, "Electronic origin of the anomalous stability of Fe-rich bcc Fe-Cr alloys," *Physical Review B. Condensed Matter and Materials Physics*, vol. 73, no. 10, pp. 104416, 2006.

[67]

J. Wallenius, S. Pillon and L. Zaboudko, "Fuels for accelerator-driven systems," *Nuclear Instruments and Methods in Physics Research Section A : Accelerators, Spectrometers, Detectors and Associated Equipment*, vol. 562, no. 2, pp. 625-629, 2006.

[68]

K. Nordlund, J. Wallenius and L. Malerba, "Molecular dynamics simulations of threshold displacement energies in Fe," *Nuclear Instruments and Methods in Physics Research Section B : Beam Interactions with Materials and Atoms*, vol. 246, no. 2, pp. 322-332, 2006.

[69]

D. Westlén and J. Wallenius, "On TiN-particle fuel based helium-cooled transmutation systems," *Annals of Nuclear Energy*, vol. 33, no. 16, pp. 1322-1328, 2006.

[70]

S. Pillon and J. Wallenius, "Oxide and nitride TRU fuels : Lessons drawn from the CONFIRM and FUTURE projects of the 5th European Framework Program," *Nuclear science and engineering*, vol. 153, no. 3, pp. 245-252, 2006.

[71]

P. Seltborg and J. Wallenius, "Proton source efficiency for heterogeneous distribution of actinides in the core of an accelerator-driven system," *Nuclear science and engineering*, vol. 154, no. 2, pp. 202-214, 2006.

[72]

M. Eriksson *et al.*, "Inherent Safety of Fuels for Accelerator-driven Systems," *Nuclear Technology*, vol. 151, no. 3, pp. 314-333, 2005.

[73]

D. Westlén and J. Wallenius, "Neutronic and Safety Aspects of a Gas-Cooled Subcritical Core for Minor Actinide Transmutation," *Nuclear Technology*, vol. 154, no. 1, pp. 41-51, 2005.

[74]

J. Wallenius and M. Eriksson, "Neutronics of minor-actinide burning accelerator-driven systems with ceramic fuel," *Nuclear Technology*, vol. 152, no. 3, pp. 367-381, 2005.

[75]

P. Olsson *et al.*, "Two-band modeling of alpha-prime phase formation in Fe-Cr," *Physical Review B. Condensed Matter and Materials Physics*, vol. 72, no. 21, pp. 1-6, 2005.

[76]

K. Tucek, J. Wallenius and W. Gudowski, "Coolant void worth in fast breeder reactors and accelerator-driven transuranium and minor-actinide burners," *Annals of Nuclear Energy*, vol. 31, no. 15, pp. 1783-1801, 2004.

[77]

J. Wallenius *et al.*, "Development of an EAM potential for simulation of radiation damage in Fe-Cr alloys," *Journal of Nuclear Materials*, vol. 329-33, pp. 1175-1179, 2004.

[78]

J. Wallenius *et al.*, "Modeling of chromium precipitation in Fe-Cr alloys," *Physical Review B Condensed Matter*, vol. 69, pp. 094103, 2004.

[79]

L. Malerba *et al.*, "Molecular dynamics simulation of displacement cascades in Fe-Cr alloys," *Journal of Nuclear Materials*, vol. 329-33, pp. 1156-1160, 2004.

[80]

M. Jolkkonen, M. Streit and J. Wallenius, "Thermo-chemical modelling of uranium-free nitride fuels," *Journal of Nuclear Science and Technology*, vol. 41, no. 4, pp. 457-465, 2004.

[81]

P. Olsson *et al.*, "Ab initio formation energies of Fe-Cr alloys," *Journal of Nuclear Materials*, vol. 321, no. 1, pp. 84-90, 2003.

[82]

E. Lindroth, J. Wallenius and S. Jonsell, "Decay rates of excited muonic molecular ions," *Physical Review A. Atomic, Molecular, and Optical Physics*, vol. 68, no. 3, 2003.

[83]

P. Seltborg *et al.*, "Definition and application of proton source efficiency in accelerator driven systems," *Nuclear science and engineering*, vol. 145, no. 3, pp. 390-399, 2003.

[84]

J. Wallenius, "Neutronic aspects of inert matrix fuels for application in ADS," *Journal of Nuclear Materials*, vol. 320, no. 02-jan, pp. 142-146, 2003.

[85]

J. Wallenius *et al.*, "Application of burnable absorbers in an accelerator-driven system," *Nuclear science and engineering*, vol. 137, no. 1, pp. 96-106, 2001.

[86]

J. Wallenius *et al.*, "Muonic atom deexcitation via formation of metastable molecular states in light of experimental verification," *Hyperfine Interactions*, vol. 138, no. 04-jan, pp. 285-288, 2001.

[87]

W. Gudowski *et al.*, "Review of the European project - Impact of Accelerator-Based Technologies on Nuclear Fission Safety (IABAT)," *Progress in nuclear energy (New series)*, vol. 38, no. 1-2, pp. 135-151, 2001.

[88]

I. Morelová *et al.*, "IAEA'S Coordinated Research Projects on Thermal Hydraulics of Fast Reactors," in *Proceedings of the 30th International Conference on Nuclear Engineering "Nuclear, Thermal, and Renewables: United to Provide Carbon Neutral Power", ICONE 2023*, 2023.

[89]

D. R. Costa *et al.*, "Coated UN microspheres embedded in UO_{2} matrix as an innovative advanced technology fuel: Early progress," in *TopFuel 2021 Light Water Reactor Fuel Performance Conference, Santander, Spain, October 24-28, 2021.*, 2021.

[90]

J. Wallenius, S. Bortot and I. Mickus, "Unprotected transients in sealer : A small lead-cooled reactor for commercial power production in Arctic Regions," in *International Conference on Physics of Reactors, PHYSOR 2018 : Reactor Physics Paving the Way Towards More Efficient Systems*, 2018, pp. 1437-1448.

[91]

J. Wallenius and M. Hussein, "Uranium nitride fuels for application in CANDU reactors," in *International Conference on Physics of Reactors, PHYSOR 2018 : Reactor Physics Paving the Way Towards More Efficient Systems*, 2018, pp. 3603-3611.

[92]

K. Lambrinou *et al.*, "Corrosion-resistant ternary carbides for use in heavy liquid metal coolants," in *Ceramic Engineering and Science Proceedings*, 2016, pp. 19-34.

[93]

F. Delage *et al.*, "ADS fuel developments in Europe : Results from the EUROTRANS integrated project," in *Energy Procedia*, 2011, pp. 303-313.

[94]

G. J. Ackland, D. J. Hepburn and J. Wallenius, "Interatomic forces for transition metals including magnetism," in *139th Annual Meeting & Exhibition - Supplemental Proceedings, Vol 2 : Materials Characterization, Computation And Modeling And Energy*, 2010, pp. 85-92.

[95]

[96]

J. Wallenius, "Micro-reactors," in *Encyclopedia of Nuclear Energy, * : Elsevier BV, 2021, pp. 749-756.

[97]

J. Wallenius, "Nitride Fuels," in *Comprehensive Nuclear Materials: Second Edition, * : Elsevier BV, 2020, pp. 88-101.

[98]

M. Jolkkonen, K. Johnson and J. Wallenius, "Fuel for water-cooled nuclear reactors," WIPO (PCT) WO2016122374A1, 2016.

[99]

J. Wallenius, M. Jolkkonen and M. Radwan, "Nitride nuclear fuel and method for its production," , 2010.

Senaste synkning med DiVA:

2024-04-12 00:24:17

**KTH Royal Institute of Technology**

*SE-100 44 Stockholm Sweden +46 8 790 60 00*